Concept for a beryllium divertor with in-situ plasma spray surface regeneration

Smith, Mark F.; Watson, R.D.; McGrath, R.T.; Croessmann, C.D.; Whitley, J.B.; Causey, R.A.

doi:10.1016/0022-3115(90)90361-p

Cited by 8 publications

(1 citation statement)

References 7 publications

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“…These results are similar to those reported in I. Dunmur's review [8]. A literature search shows that more recent activities in plasma spraying of beryllium have been directed towards the application of in situ repair and surface regeneration of divertor regions in fusion reactors [16,17,18]. To date, plasma spraying of beryllium has not been reported since the activities performed at Battelle, Columbus.…”

Section: Strain Tosupporting

confidence: 84%

Beryllium processing technology review for applications in plasma-facing components

Castro¹,

Jacobson²,

Stanek³

1993

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Materials research and development activities for the International Thermonuclear Experimental Reactor (ITER), i.e., the next generation fusion reactor, are investigating beryllium as the first-wall containment material for the reactor. Important in the selection of beryllium is the ability to process, fabricate and repair beryllium first-wall components using existing technologies. Two issues that will need to be addressed during the engineering design activity will be the bonding of beryllium tiles in high-heat-flux areas of the reactor, and the in situ repair of damaged beryllium tiles. The following review summarizes the current technology associated with welding and joining of beryllium to itself and other materials, and the state-of-theart in plasma-spray technology as an in situ repair technique for damaged beryllium tiles. In addition, a review of the current status of beryllium technology in the former Soviet Union is also included.

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Section: Strain Tosupporting

confidence: 84%

Beryllium processing technology review for applications in plasma-facing components

Castro¹,

Jacobson²,

Stanek³

1993

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Plasma-Sprayed Beryllium on Macro-Roughened Substrates for Fusion Reactor High Heat Flux Applications

et al. 2007

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The development of beryllium first wall (FW) plasma facing components for future magnetic confinement fusion experiments, such as the International Thermonuclear Experimental Reactor (ITER), is a topic of great importance as research into long-term energy sources increases in urgency. The FW components must be able to survive the harsh plasma environment for extended periods of time. One proposed method for initial fabrication and repair of FW components is plasma spraying. Previous plasma-sprayed beryllium mock-up FW components had coating separation from the substrate at the edges. The present work describes experiments to produce beryllium mock-up FW components by plasma spray deposition on macro-roughened substrates. Experimental parameters, high heat flux testing and characterization results from the components are presented. No separation of the coating from the substrate was observed. Results of high heat flux testing under electron beam irradiation show performance exceeding that required for ITER FW components. Differences in macro-roughening features result in changes in the threshold absorbed heat flux before damage to the coatings occurs.

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Optimizing the thermal conductivity of vacuum plasma-sprayed beryllium for fusion applications

Castro

Stanek

Elliott

et al. 1995

Journal of Nuclear Materials

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Concept for a beryllium divertor with in-situ plasma spray surface regeneration

Cited by 8 publications

References 7 publications

Beryllium processing technology review for applications in plasma-facing components

Beryllium processing technology review for applications in plasma-facing components

Plasma-Sprayed Beryllium on Macro-Roughened Substrates for Fusion Reactor High Heat Flux Applications

Optimizing the thermal conductivity of vacuum plasma-sprayed beryllium for fusion applications

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